In this project, 1 MeV Kr ions will be used to irradiate Sm3TaO7, Y3TaO7, Eu3TaO7, Gd3TaO7 and Lu3TaO7 (up to 30 dpa) at 200 K, RT, 450 K, and 600 K to study the radiation tolerance and structural evolution in these nuclear waste form matrix materials. DF/BF images and SAED patterns will be collected at various fluences to observe the structural modifications induced, as well as the specific temperatures and ion fluences at which these modifications occur. In addition, ion irradiation-induced microstructural evolution, including defect evolution and phase transformations, will be compared among these weberite-type compounds.
This project needs one-week of observation time at the IVEM facility. We anticipate observing the formation and evolution of defects, including point defects, dislocation loops, and stack faults, as well as phase transformation processes, as a function of fluence and temperature. By comparing the radiation responses of these compounds, we will obtain insight into the manner in which temperature and composition affect the radiation tolerance of weberite-type phases, thus helping to design radiation tolerant materials in this system for next generation nuclear waste matrices.
The Office of Used Nuclear Fuel Disposition Research and Development (UNFD R&D) is investigating various geologic media and concepts for the disposal of spent nuclear fuel (SNF) and HLW that exists today and that will be generated under future fuel cycles. For long-term disposition, the performance and safety of the nuclear waste form, which immobilizes waste within a geologic repository, is a critical aspect of the back-end of the nuclear fuel cycle. Ln3TaO7 weberite compounds are promising candidates for providing reliable and stable long-term immobilization, as they combine high radionuclide incorporation with exceptional stability under irradiation (often superior to previously-studied complex oxide waste forms).In this project, study of the atomic structure evolution and radiation tolerance of Ln3TaO7 weberite-type compounds in simulated disposal environments will contribute to understanding of the mechanisms of radiation damage in this and related complex oxide waste forms, and will further promote the development of HLW form matrix materials. Characterization of the compositional variation in radiation tolerance will contribute to the design of improved immobilized materials with superior properties and performance.